ML20196E217
From kanterella
| ML20196E217 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 11/30/1988 |
| From: | SARGENT & LUNDY, INC. |
| To: | |
| Shared Package | |
| ML20196E192 | List: |
| References | |
| SL-4492, SL-4492-R01, SL-4492-R1, NUDOCS 8812090294 | |
| Download: ML20196E217 (85) | |
Similar Documents at Byron | |
|---|---|
Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20217P6351999-09-29029 September 1999
[Table view]Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20207H7561999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20207H7621999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20204H9941999-03-0303 March 1999 Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20207H7671998-10-0505 October 1998 Rv Weld Chemistry & Initial Rt Ndt ML20236U4751998-07-23023 July 1998 SG Eddy Current Insp Rept Cycle 7 Refueling Outage (B2R07) ML20198J5641998-01-0707 January 1998 Unit 2 Pressure & Temp Limits Rept ML20198J5061998-01-0707 January 1998 Pressure Temp Limits Rept (Ptlr) ML20198J5201998-01-0707 January 1998 Pressure Temp Limits Rept (Ptlr) ML20198J5531998-01-0707 January 1998 Unit 1 Pressure & Temp Limits Rept ML20199E8801997-11-0303 November 1997 Revised Byron Unit 2 Pressure Temperature Limits Rept (PTLR) ML20199E8751997-11-0303 November 1997 Revised Byron Unit 1 Pressure Temperature Limits Rept (Ptlr) ML20217G6171997-07-22022 July 1997 Operability Assessment Process Form ML20141K0241997-05-21021 May 1997 Pressure & Temp Limits Rept ML20141K0431997-05-21021 May 1997 Pressure & Temp Limits Rept ML20141K0181997-05-21021 May 1997 Pressure & Temp Limits Rept ML20141K0371997-05-21021 May 1997 Pressure & Temp Limits Rept ML20148P8811997-05-16016 May 1997 Spent Fuel Rack Criticality Analysis Using Soluble B Credit ML20141F7141997-05-15015 May 1997 Operability Assessment Process Form ML20134M3131996-11-13013 November 1996 Revised SG Tube Rupture Analysis for Byron/Braidwood ML20134N8011996-10-31031 October 1996 Spent Fuel Rack Criticality Analysis W/Credit for Soluble Boron ML20134N3131996-10-31031 October 1996 Sys Design Description for Containment Spray ML20129F8921996-09-30030 September 1996 Circumferential Indication Summary Rept ML20129G3881996-08-31031 August 1996 Unit-1 EOC 7B Interim Plugging Criteria Rept ML20113B0951996-06-30030 June 1996 Interim Plugging Criteria Return to Power Rept ML20101E7651996-03-31031 March 1996 Unit - 1 EOC 7A Interim Plugging Criteria Rept ML20095G0691995-12-31031 December 1995 Interim Plugging Criteria Return to Power Rept ML20093G7171995-10-12012 October 1995 Rev 0 to PSA-B-95-18, RELAP5M3 Comparison of Model Boiler 2 MSLB from Hzp Test ML20093G8821995-10-11011 October 1995 Rev 0 to PSA-B-95-17, Calculation of Byron 1/Braidwood 1 D4 SG Tube Support Plate Loads w/RELAP5M3 ML20092A9731995-09-0101 September 1995 Independent Verification of Byron/Braidwood D4 SG Tube Support Plate Differential Pressures During Mslb ML20091M8711995-08-25025 August 1995 Rept of Independent Assessment of Calculation of TSP Forces ML20078P1551995-02-0606 February 1995 Probability of Detection by Bobbin Insp ML20078G8351995-01-25025 January 1995 Probability of Detection by Bobbin Insp ML20078F1861995-01-20020 January 1995 Refuel Outage B1R05 RHR HX Nozzles Ultrasonic Indication Summary ML20078G9431995-01-19019 January 1995 EOC 6 Interim Plugging Criteria Rept ML20078R1161994-11-15015 November 1994 Non-proprieatry NFSR-0090, Response to Nuclear Regulatory Staff Request for Addl Info on VIPRE/WRB-2 DNBR Thermal Limit for Westinghouse 17x17 Ofa & Vantage 5 Fuel ML20149H1591994-06-30030 June 1994 Spent Fuel Rack Criticality Analysis Considering Boraflex Gaps & Shrinkage ML20127L0091992-09-0808 September 1992 Rev 0,to VIPRE/WRB-2 DNBR Thermal Limit for Westinghouse 17x17 Ofa & Vantage 5 Fuel ML20087E0451992-01-0909 January 1992 UHS Design Basis Reconstitution Final Rept ML20077D0671991-11-15015 November 1991 Nonproprietary Version of Rev 0 to Boric Acid Corrosion of Oconee Unit 1 Upper Tubesheet ML20082K7641991-08-22022 August 1991 Simulator Initial Certification Rept,Sept 1991 ML20064N8021991-07-27027 July 1991 Byron/Braidwood Units 1 & 2 Increased Main Steam Safety Valve Setpoint Tolerance Safety Evaluation ML20101F5631991-07-0303 July 1991 Byron/Braidwood Unit 1 Rhr/Safety Injection Piping Water Hammer Acoustic Analysis L-90-469, Byron/Braidwood Units 1 & 2 Increased Main Steam Safety Valve Setpoint Tolerance Safety Evaluation1990-10-31031 October 1990 Byron/Braidwood Units 1 & 2 Increased Main Steam Safety Valve Setpoint Tolerance Safety Evaluation ML20042E9131990-03-31031 March 1990 Nonproprietary Rev 1 to Steam Generator Tube Rupture Analysis for Byron & Braidwood Plants. ML20246D6871989-08-14014 August 1989 Rev 1 to Criticality Analysis of Byron & Braidwood Station High Density Fuel Racks ML19327B4011989-07-31031 July 1989 Safety Evaluation for Byron/Braidwood Stations Units 1 & 2 Transition to Westinghouse 17 X 17 Vantage 5 Fuel. ML20247H0711989-06-30030 June 1989 Description & Verification Summary of Computer Program, Gappipe ML20246D6711989-06-30030 June 1989 Criticality Analysis of Byron/Braidwood Fresh Fuel Racks ML20247H0791989-06-22022 June 1989 App to Description & Verification Summary of Computer Program,Gappipe 1999-09-29 Category:TEXT-SAFETY REPORT MONTHYEARML20217H5221999-09-30030 September 1999
[Table view]Monthly Operating Repts for Sept 1999 for Byron Station, Units 1 & 2.With ML20217P6351999-09-29029 September 1999 Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212B9261999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Byron Station,Units 1 & 2.With ML20210R3431999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Byron Station, Units 1 & 2.With ML20210E2251999-07-21021 July 1999 B1R09 ISI Summary Rept Spring 1999 Outage, 980309-990424 ML20209G1751999-07-0808 July 1999 SG Eddy Current Insp Rept,Cycle 9 Refueling Outage (B1R09) ML20207H7941999-06-30030 June 1999 Rev 0 to WCAP-15180, Commonwealth Edison Co Byron,Unit 2 Surveillance Program Credibility Evaluation ML20207H8071999-06-30030 June 1999 Rev 0 to WCAP-15178, Byron Unit 2 Heatup & Cooldowm Limit Curves for Normal Operations ML20207H7851999-06-30030 June 1999 Rev 0 to WCAP-15183, Commonwealth Edison Co Byron,Unit 1 Surveillance Program Credibility Evaluation ML20207H7771999-06-30030 June 1999 Rev 0 to WCAP-15177, Evaluation of Pressurized Thermal Shock for Byron,Unit 2 ML20209H3711999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Byron Station, Units 1 & 2.With ML20207H7561999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20207H7621999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20195J8001999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Byron Station,Units 1 & 2.With ML20207B6481999-05-25025 May 1999 SER Accepting Revised SGTR Analysis for Byron & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations ML20206R6991999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Byron Station Units 1 & 2.With ML20195C7961999-04-28028 April 1999 Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A) M980023, Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A)1999-04-28028 April 1999 Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A) ML20205P7001999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Byron Station,Units 1 & 2.With ML20205B5091999-03-26026 March 1999 SER Accepting Relief Requests 12R-24,Rev 0 & 12R-34,Rev 0, Related to Second 10-year Interval Inservice Insp for Byron Station,Units 1 & 2 ML20205C5101999-03-21021 March 1999 Revised Safety Evaluation Supporting Improved TS Amends Issued by NRC on 981222 to FOLs NPF-37,NPF-66,NPF-72 & NPF-77.Revised Pages Include Editorial Corrections ML20204G3831999-03-19019 March 1999 Safety Evaluation Accepting Second 10-yr Interval ISI Request for Relief 12R-11 M990004, Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function1999-03-17017 March 1999 Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function ML20206A8831999-03-17017 March 1999 Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20204H9941999-03-0303 March 1999 Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20204C7671999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Byron Station,Units 1 & 2.With ML20199G8271998-12-31031 December 1998 Rev 1 Comm Ed Byron Nuclear Power Station,Unit 1 Cycle 9 Startup Rept ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with ML20202F6181998-12-31031 December 1998 Cycle 8 COLR in ITS Format & W(Z) Function ML20206B4001998-12-31031 December 1998 Annual & 30-Day Rept of ECCS Evaluation Model Changes & Errors for Byron & Braidwood Stations ML20199E6371998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Byron Station,Units 1 & 2.With ML20202F6021998-12-31031 December 1998 Cycle 9 COLR in ITS Format & W(Z) Function ML20196K6731998-12-31031 December 1998 10CFR50.59 Summary Rept for 1998 ML20207H7731998-11-30030 November 1998 Rev 0 to WCAP-15125, Evaluation of Pressurized Thermal Shock for Byron,Unit 1 ML20207H8011998-11-30030 November 1998 Rev 0 to WCAP-15124, Byron Unit 1 Heatup & Cooldown Limit Curves for Normal Operation ML20198D1501998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Byron Nuclear Power Station,Units 1 & 2.With ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB ML20195F8321998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Byron Nuclear Power Station,Units 1 & 2.With 05000454/LER-1998-018, Corrected LER 98-018-00:on 980912,inoperable Unit 1 DG Was Noted.Caused by Low Lube Oil Pressure Condition.Immediately Entered Into Lcoar for AC Sources TS 3.8.1.1,Action a1998-10-0909 October 1998 Corrected LER 98-018-00:on 980912,inoperable Unit 1 DG Was Noted.Caused by Low Lube Oil Pressure Condition.Immediately Entered Into Lcoar for AC Sources TS 3.8.1.1,Action a ML20207H7671998-10-0505 October 1998 Rv Weld Chemistry & Initial Rt Ndt ML20154L5501998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Byron Nuclear Power Station,Units 1 & 2.With ML20197C9051998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Byron Nuclear Power Station,Units 1 & 2.With ML20151Z9651998-08-31031 August 1998 Revised MOR for Aug 1998 for Byron Nuclear Power Station. Rept Now Includes Page 9 Which Was Omitted from Previously Issued Rept ML20238F6551998-08-28028 August 1998 SE Authorizing Licensee Request for Relief NR-20,Rev 1 & NR-25,Rev 0 Re Relief from Examination Requirement of Applicable ASME BPV Code,Section XI for First ISI Interval Exams ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20237B3361998-08-14014 August 1998 B2R07 ISI Summary Rept,Spring 1998 Outage, 961005-980518 ML20237B4841998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Byron Nuclear Power Station Units 1 & 2 1999-09-30 |
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